Draft

ADVISORY BOARD ON 

RADIATION AND WORKER HEALTH 

National Institute for Occupational Safety and Health 

SC&A’S EVALUATION OF CS-137/SR-90 VALUES AND 

ACTINIDES USING INL WASTE REPORTS 

IN RELATIONSHIP TO ASSIGNING INTAKES

Contract No. 211-2014-58081 

SCA-TR-2016-SEC007, Revision 0 

Prepared by 

Ron Buchanan, PhD, CHP

SC&A, Inc.

1608 Spring Hill Road, Suite 400 

Vienna, Virginia 22182 

Saliant, Inc.

5579 Catholic Church Road 

Jefferson, Maryland 21755 

June 2016 

DISCLAIMER

This is a working document provided by the Centers for Disease Control and Prevention (CDC) technical 

support contractor, SC&A for use in discussions with the National Institute for Occupational Safety and 

Health (NIOSH) and the Advisory Board on Radiation and Worker Health (ABRWH), including its 

Working Groups or Subcommittees. Documents produced by SC&A, such as memorandum, white paper, 

draft or working documents are not final NIOSH or ABRWH products or positions, unless specifically 

marked as such. This document prepared by SC&A represents its preliminary evaluation on technical 

issues.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.
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SC&A, INC.: Technical Support for the Advisory Board on Radiation & 

Worker Health Review of NIOSH Dose Reconstruction Program

DOCUMENT TITLE: 

SC&A’s Evaluation of Cs-137/Sr-90 Values and Actinides Using INL 

Waste Reports in Relationship to Assigning Intakes

DOCUMENT NUMBER/

DESCRIPTION:

SCA-TR-2016-SEC007 

REVISION NO.: 0

SUPERSEDES: N/A

EFFECTIVE DATE: June 24, 2016

TASK MANAGER: John Stiver, MS, CHP [signature on file]

PROJECT MANAGER: John Stiver

DOCUMENT 

REVIEWER(S): Joe Fitzgerald, John Stiver [signatures on file] 

Record of Revisions

Revision 

Number

Effective 

Date Description of Revision

0 (Draft) 06/24/2016 Initial issue
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TABLE OF CONTENTS

Abbreviations and Acronyms ..........................................................................................................4

Executive Summary.........................................................................................................................6

1.0 Introduction and Background ..............................................................................................8

2.0 CS-137/SR-90 Values ...........................................................................................................8

3.0 Actinide/SR-90 and Actinide/CS-137 Values ....................................................................11

4.0 Summary and Conclusions ................................................................................................14

5.0 References ..........................................................................................................................16

Appendix A: Cs-137/Sr-90 Values for Major INL Facilities ........................................................17

Appendix B: Actinide/SR-90 Values .............................................................................................20

Appendix C: Actinide/Cs-137 Values ...........................................................................................23

Attachment 1. Documents and Data Used In Evaluation of CS/SR and Actinides ........................26
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ABBREVIATIONS AND ACRONYMS

ABRWH Advisory Board on Radiation and Worker Health

Ac actinium

Al aluminum 

Am americium

ANP Aircraft Nuclear Propulsion 

ATR Advance Test Reactor

BNL Brookhaven National Laboratory 

Ce cerium

CFA Central Facility Area

CFR Code of Federal Regulations

Ci curie

Cm curium

Co cobalt

CPP Chemical Processing Plant

Cs cesium

d day 

DR dose reconstruction

D&D decontamination and decommissioning

ER evaluation report

ETR Engineering Test Reactor 

Eu europium 

FAP fission and activation product 

ICPP Idaho Chemical Processing Plant

INEL Idaho National Engineering Laboratory 

INL Idaho National Laboratory 

liq liquid

Meas Measured 

μCi microcurie

μCi/ml, uCi/ml microcurie per milliliter

MTR Materials Testing Reactor

Nb niobium 
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Np neptunium 

NIOSH National Institute for Occupational Safety and Health

NRTS National Reactor Testing Station

ORAUT Oak Ridge Associated Universities Team 

OTIB Occupational Technical Information Bulletins 

Pa protactinium 

PBF Power Burst Facility

Pm promethium 

Pr praseodymium 

Pu plutonium 

Ru ruthenium 

SEC Special Exposure Cohort 

SPERT Special Power Excursion Reactor Test

Sr strontium 

SRDB Site Research Database

SS stainless steel

TAN Test Area North

Th thorium 

TKBS Site Technical Basis Document

TRA Test Reactor Area

U uranium 

WER Waste Experimental Reduction

WMC Waste Management Complex

y year

Zr zirconium 
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EXECUTIVE SUMMARY

In the National Institute for Occupational Safety and Health’s (NIOSH’s) evaluation report (ER) 

for the Idaho National Laboratory (INL) Special Exposure Cohort (SEC) petition SEC-00219 of 

March 12, 2015 (NIOSH 2015), one of the major assumptions was that a bioassayed indictor 

radionuclide [strontium-90 (Sr-90) and/or cesium-137 (Cs-137)] can be used to assign 

dosimetric-significant fission and activation product (FAP) and actinide (alpha emitter) intakes 

using the ratio method. This method requires that radionuclide ratios remain fairly constant for 

the many processes and locations, and over most of the operating history of INL. 

In view of INL’s numerous types of reactors, experimental charter, and the various fuels and 

materials shipped in from other sites for processing, SC&A performed a preliminary analysis of 

some of the available INL bioassay, Brookhaven National Laboratory (BNL) fuel, and swipe 

data in 2015 to obtain an indication of the validity of this assumption (SC&A 2015). As outlined 

in that report, SC&A found there were indications that the Cs-137/Sr-90 values were not always 

centered on unity. SC&A then searched for documentation of quantitative analyses of the fuel 

elements processed in the dissolver at the Idaho Chemical Processing Plant (ICPP) in order to 

determine the radionuclide components that workers may have been exposed to; however, such 

documentation has not been located to date. Therefore, SC&A searched the Site Research 

Database (SRBD) for other documents that could provide quantitative radionuclide data. During 

this search, SC&A located numerous INL waste reports that contained quantitative Cs-137 and 

Sr-90 measurements performed on the same samples (some also contained actinide analyses in 

the later years); these reports spanned a relatively long time period (1957–1993) for the major 

operational areas within INL. Quantitative radionuclide data for waste materials (air, liquid, and 

solid) at the INL facilities provide a good representation of the potential intake exposures to 

workers. Therefore, these data were analyzed in detail to evaluate if there is a reasonably 

consistent relationship between the Cs-137/Sr-90 concentrations, and if these indicating 

radionuclides could be used to assign other radionuclide intakes such as FAPs for dose 

reconstruction (DR) purposes. In addition, quantitative actinide data in relationship to Sr-90 and 

Cs-137 were analyzed when available. Data for the ICPP were not analyzed for the period 1963–

1974, because this was the period of the SEC. 

Cs-137/Sr-90 

A total of 251 matched pairs of measured Cs-137 and Sr-90 activities were located and analyzed, 

spanning the period 1957–1993 for a number of major facilities at the INL site. Of these 251 

matched pairs of data, 33% contained Cs-137/Sr-90 values centered on unity, within a factor of 2 

(i.e., Cs-137/Sr-90 = 0.5 to 2.0). The remaining Cs-137/Sr-90 values were outside this interval, 

with values ranging from 0.04 to 2,587. The Cs-137/Sr-90 values are separated according the 

major facilities in Appendix A of this report. 

Actinides/Sr-90 

A total of 59 matched pairs of measured Sr-90 and an actinide [americium-241 (Am-241), 

plutonium-238 (Pu-238), Pu-239, uranium-234 (U-234), or U-236] activity were located and 

analyzed, spanning the period 1970–1995 for various facilities at the INL site. The measured 

actinide/Sr values were compared to the actinide/Sr values recommended in Table 5-22 of 

ORAUT-TKBS-0007-5, Idaho National Laboratory and Argonne National Laboratory – West – 

Occupational Internal Dose, Revision 3. A comparison ratio value centered on 1.0 would 
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indicate agreement between the measured and recommended values; however, ratio values not 

centered on unity would indicate insufficient, or excessive, actinide intake assignments during 

DR. Of these 59 matched pairs, 7% contained actinide/Sr values centered on unity, within a 

factor of 2 (i.e., actinide/Sr = 0.5 to 2.0). The remaining actinide/Sr values were outside this 

interval, some ranging orders of magnitude away from unity. The actinide/Sr-90 values are 

illustrated in Appendix B of this report. The results were not separated according to the major 

facilities because of the low number of matched pairs for each individual facility.

Actinides/Cs-137 

A total of 72 matched pairs of measured Cs-137 and an actinide (Am-241, Pu-238, Pu-239, U234, or U-236) activity were located and analyzed, spanning the period 1970–1995 for various 

facilities at the INL site. The measured actinide/Cs values were compared to the actinide/Cs 

values recommended in Table 5-23 of ORAUT-TKBS-0007-5. A comparison ratio value 

centered on 1.0 would indicate agreement between the measured and recommended values; 

however, ratio values not centered on unity would indicate insufficient, or excessive, actinide 

intake assignments during DR. Of these 72 matched pairs, 11% contained actinide/Cs values 

centered on unity, within a factor of 2 (i.e., actinide/Cs = 0.5 to 2.0). The remaining actinide/Cs 

values were outside this interval; some ranging orders of magnitude away from unity. The 

actinide/Cs-137 values are illustrated in the Appendix C of this report. The results were not 

separated according to the major facilities because of the low number of matched pairs for each 

individual facility.

These results indicate that at INL the Cs-137/Sr-90 values may not be sufficiently centered on 

unity as required by ORAUT-OTIB-0054, Fission and Activation Product Assignment for 

Internal Dose-Related Gross Beta and Gross Gamma Analyses, Revision 03, for assigning FAP 

intakes. Also, actinide/Sr, or actinide/Cs, values may not be sufficiently constant (or known) as 

required by ORAUT-TKBS-0007-5 (Tables 5-22 and 5-23) for assigning actinide intakes, even 

in situations where it can be assumed that the actinides are tied to an indicating radionuclide, 

such as Sr-90 or Cs-137. 
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1.0 INTRODUCTION AND BACKGROUND

NIOSH responded to INL SEC-00219 in an ER of March 12, 2015 (NIOSH 2015). In that ER, 

and also in the technical basis document for INL (ORAUT-TKBS-0007-5), NIOSH’s basis for 

assigning internal intakes/doses for most years and locations at the INL (except those covered by 

NIOSH’s proposed SEC class and the reserved areas/dates) relies on the important assumption

that the Cs-137/Sr-90 values are approximately unity, that FAPs are directly tied by a known 

ratio to Sr-90 or Cs-137 (as per ORAUT-OTIB-0054), and that actinides are directly tied by a 

known ratio to Sr-90 or Cs-137 (as per Tables 5-22 and 5-23 of ORAUT-TKBS-0007-5).

In a previous evaluation using a relatively small sampling of bioassay and swipe data 

(SC&A 2015), SC&A found indications that the measured Cs-137/Sr-90 values were not 

centered on unity, and that the measured actinide/Sr or actinide/Cs values were not constant or 

representative of those recommended in ORAUT-TKBS-0007-5. Therefore, SC&A searched for 

further documentation of measured quantitative radionuclide analyses of Sr-90, Cs-137, and 

actinide activity. Searches for documentation of quantitative analyses of the fuel elements 

processed in the dissolver at the ICPP have not produced significant data to date. The INL 

electronic bioassay database, which may provide additional quantitative radionuclide matchedpair data in the near future, is currently in the process of being completed and verified. 

In the process of searching the SRDB, SC&A located INL waste management reports that 

contained quantitative Sr-90 and Cs-137 measurements performed on the same samples (some 

also contained actinide analyses in the later years); these reports span a relatively long time 

period (1957–1993) and cover a number of the major operational areas within INL. These data 

provide a good representation of the materials workers were exposed to, and the potential intake

mixtures. These data were obtained by performing an SRDB search using the keywords “Waste 

Report,” “Radioactive Waste,” and “Radioactive Waste Report.” A list of the documents that 

contained useful radionuclide measures, and some of the recorded data that were used in this 

evaluation, is provided in Attachment 1 of this report. Analyses of these data are provided in the 

following sections. 

2.0 CS-137/SR-90 VALUES

NIOSH’s ER and ORAUT-TKBS-0007-5 rely heavily on the use of ORAUT-OTIB-0054 to 

assign FAP intakes using Sr-90 or Cs-137 as the indicating radionuclide for numerous other FAP 

radionuclides at INL for most locations and time periods. An example of Table 7-3a from 

ORAUT-OTIB-0054 is provided here as Figure 1. As can be seen from this table, assignment of 

FAP intakes is dependent on the Cs-137/Sr-90 value being approximately 1.0. 
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Figure 1. Table 7-3a, FAP-to-Sr-90 or -Cs-137 Ratios for ATR-1 (ORAUT-OTIB-0054) 

SC&A located a total of 251 matched pairs of measured Cs-137 and Sr-90 activity in the INL 

waste reports, spanning the period 1957–1993 for the INL site. SC&A analyzed these data to 

determine the Cs-137/Sr-90 values for each matched pair for the INL site, and then separated 

them according to the major individual facilities. Only recorded and paired data points 

specifically listing Cs-137 and Sr-90 in units of activity (μCi, Ci, etc.) on the same material were 

used in these analyses; this included air, liquid, and solid waste. Figure 2 contains the results for 

the 251 INL data pairs analyzed.

Figure 2. Cs-137/Sr-90 Values for 251 Data Pairs from INL Waste Reports 

All of INL

 Waste Documents 1955-1995

0.01

0.10

1.00

10.00

100.00

1,000.00

10,000.00

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.04 to <0.5] Cs/Sr [Range 0.5 to 2.0] Cs/Sr [>2.0 to 2,587]
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Of the 251 pairs, 33% contained Cs-137/Sr-90 values centered on unity, within a factor of 2 (i.e., 

Cs-137/Sr-90 = 0.5 to 2.0); these are represented by the diamonds in the plot. The remaining Cs137/Sr-90 values (squares for <0.5 and triangles for >2.0) were outside this interval, with values 

ranging from 0.04 to 2587. 

The Cs-137/Sr-90 values were separated according to the major INL facilities; those plots are 

provided in Appendix A. Table 1 is a summary of the results for all of INL and also broken down 

by individual facilities.

Table 1. Summary of Cs-137/Sr-90 Values for INL and Various Facilities 

Facility No. of Pairs

No. of Pairs with 

Cs/Sr

Value of 0.5 to 2.0

% of Pairs with 

Cs/Sr

Value of 0.5 to 2.0

CFA, etc. 32 12 38%

ICPP 71 38 54%

TAN & ANP 73 22 30%

TRA 75 12 16%

INL (total) 251 84 33%

As can be seen from Table 1, the majority of the Cs-137/Sr-90 values were not centered on unity. 

SC&A had previously analyzed a relatively small sample of bioassays, BNL Fuels, and smears 

(SC&A 2015). These data are summarized in Figure 3.

Figure 3. Summary of Cs-137/Sr-90 Values from Bioassays, BNL Fuel, and Smears 

Bios, Nose Swabs, BNL Fuel, & Smears 1960-2010

0.01

0.10

1.00

10.00

100.00

1,000.00

10,000.00

1960 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.02 to <0.5] Cs/Sr [0.5 to 2.0] Cs/Sr [>2.0 to 6911]
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Comparison of the Cs-137/Sr-90 values in Figure 2 and Figure 3 indicates that the data from the 

INL waste reports are compatible with the previous bioassay, BNL fuel, and smear data. 

3.0 ACTINIDE/SR-90 AND ACTINIDE/CS-137 VALUES

According to NIOSH’s ER, the basis for assigning actinide intakes, except for special situations, 

is directly tied (in a constant ratio) to an indicating radionuclide (Sr-90 or Cs-137) using 

Table 5-22 (Sr-90 ratios) and/or Table 5-23 (Cs-137 ratios) of ORAUT-TKBS-0007-5. These 

tables are reproduced here as Figures 4 and 5. 

Figure 4. Table 5-22, Actinide-to-Sr90 Ratios (ORAUT-TKBS-0007-5) 

Figure 5. Table 5-23, Actinide-to-Cs-137 Ratios (ORAUT-TKBS-0007-5) 
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Because this method involves assigning actinide intakes and doses over a long time span and 

numerous areas/operations, it results in the majority of the internal alpha dose assignments for 

INL workers who did not have specific actinide radionuclide bioassays. Therefore, SC&A used 

measured actinide/Sr-90 and actinide/Cs-137 values to determine if the ratio values 

recommended in Tables 5-22 and 5-23, respectively, are applicable to DR for INL workers. The 

major dose contributors in these tables are from Am-241, Pu-238, Pu-239, U-234, and U-236; 

therefore, these were the radionuclides evaluated in this analysis. SC&A determined the value of 

the measured actinide/Sr-90 (or actinide/Cs-137) and compared that value to the recommended 

value in Table 5-22 (or Table 5-23) to obtain a relative ratio. A relative ratio centered on unity 

indicates that the measured value is in agreement with the recommended value. A ratio >1.0 

indicates that the measured value would assign an intake greater than that recommended in the 

tables, and a ratio <1.0 indicates that the measured value would assign an intake less than that 

recommended in the tables.

SC&A analyzed the waste report data for all of INL; the results were not separated according to 

the major facilities because of the low number of matched pairs for each individual facility. Only 

recorded and paired data points specifically listing an actinide and Sr-90 (and/or Cs-137) in units 

of activity (μCi, Ci, etc.) on the same material were used in this analyses; this included air, 

liquid, and solid waste. Figure 6 contains the results for the 26 Pu-238/Sr-90 data pairs analyzed.

Figure 6. Measured Pu-238/Sr-90 Values Compared to 

Table 5-22 from ORAUT-TKBS-0007-5 

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Pu-238/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of Pu238/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of Pu238/Sr

In this case, only 1 (shown as a diamond in Figure 6) of the 26 Pu-238/Sr-90 data pairs fell 

within the 0.5 to 2.0 range; the other ratios (squares in Figure 6) had a wide range of values.
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Figure 7 contains the results for the 29 Pu-238/Cs-137 data pairs analyzed.

Figure 7. Measured Pu-238/Cs-137 Values Compared to 

Table 5-23 from ORAUT-TKBS-0007-5 

In this case, 7 (diamonds in Figure 7) of the 29 Pu-238/Cs-137 data pairs fell within the 0.5 to 

2.0 range; the other ratios (squares) had a wide range of values.

The actinide/Sr-90 values for 59 data pairs were also analyzed for Am-241, Pu-239, U-234, and 

U-236. These results are contained in figures shown in Appendix B. Table 2 summarizes the 

results for INL for the five actinide radionuclides evaluated. 

Table 2. Summary of Measured Actinide/Sr-90 Values Compared to Ratio Values 

Recommended in Table 5-22 of ORAUT-TKBS-0007-5 

Radionuclide No. of Pairs 

No. of Pairs

With Ratio

Value of 0.5 to 2.0

% of Pairs

With Ratio

Value of 0.5 to 2.0

Am-241 7 2 29%

Pu-238 26 1 4%

Pu-239 9 1 11%

U-234 13 0 0%

U-236 4 0 0%

Total: 59 4 7%

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Pu-238/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of Pu238/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of Pu238/Cs
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The actinide/Cs-137 values for 72 data pairs were also analyzed for Am-241, Pu-239, U-234, and 

U-236. These results are contained in figures as shown in Appendix C. Table 3 summarizes the 

results for INL for the five actinide radionuclides evaluated. 

Table 3. Summary of Measured Actinide/Cs-137 Values Compared to Ratio Values 

Recommended in Table 5-23 of ORAUT-TKBS-0007-5 

Radionuclide No. of Pairs 

No. of Pairs

With Ratio

Value of 0.5 to 2.0

% of Pairs

With Ratio

Value of 0.5 to 2.0

Am-241 11 1 9%

Pu-238 29 7 24%

Pu-239 11 0 0%

U-234 17 0 0%

U-236 4 0 0%

Total: 72 8 11%

As can be seen from Tables 2 and 3, the majority of the measured-to-recommended values were 

not centered on unity. 

4.0 SUMMARY AND CONCLUSIONS 

This investigation indicates the following, based on the measured data points analyzed to date:

• Cs-137/Sr-90 – The majority of the Cs-137/Sr-90 values were not centered on unity. 

Only 33% of 251 data points analyzed for Cs-137/Sr-90 from the 1957–1993 INL waste 

reports fell within a range of 0.5–2.0. Some ratio values were orders of magnitude above 

and below unity. 

• Use of ORAUT-OTIB-0054 – This document is based on the Cs-137/Sr-90 value being 

centered on unity. Therefore, using it to assign FAP intakes based on Sr-90 bioassays 

compared to Cs-137 bioassays would produce significantly different intakes/doses in 

many cases, because at INL the materials the workers were exposed to did not always

contain equal activities of Cs-137 and Sr-90. For example, potentially, two workers with 

the same intakes, but one bioassayed for Sr-90 and the other bioassayed for Cs-137, 

would be assigned very different intakes/doses using ORAUT-OTIB-0054 due to the 

difference in the actual Sr-90 and Cs-137 contents of the materials detected in the 

bioassays.

• Actinide/Sr-90 – The majority of the measured actinide-to-Sr-90 values were different 

from those recommended in ORAUT-TKBS-0007-5, Table 5-22. Only 7% of the 59 data 

pairs matched the actinide-to-Sr-90 ratios recommended in Table 5-22 within a factor of 

2. Some ratios were orders of magnitude above and below those recommended. 

• Actinide/Cs-137 – The majority of the measured actinide to Cs-137 values were different 

from those recommended in ORAUT-TKBS-0007-5, Table 5-23. Only 11% of the 72 
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data pairs matched the actinide-to-Cs-137 ratios recommended in Table 5-23 within a 

factor of 2. Some ratios were orders of magnitude above and below those recommended.

• Use of only Sr-90 or Cs-137 – Evaluating the numerous plots in Appendices B and C 

indicates that the sole use of Sr-90 or Cs-137 does not offer an advantage in consistency 

when assigning actinide intakes. 

Comparing the results obtained from the waste reports to those obtained previously using 

bioassays, BNL fuels, and smears (SC&A 2015) indicates similar issues with using the ratio 

method at INL. 

Considering these findings, using an indicating radionuclide (such as Sr-90 and/or Cs-137) to 

assign FAP and actinide intakes at INL does not appear to provide a method that results in 

assigning intakes that are indicative of the materials the workers were actually exposed to.

Additional information concerning measured radionuclide ratios can be analyzed when the 

complete INL bioassay database becomes available, and if quantitative analyses of ICPP 

dissolver feed material are located.
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5.0 REFERENCES

NIOSH. 2015. SEC Petition Evaluation Report – INL Petition SEC-00219 of September 16, 

2014, National Institute for Occupational Safety and Health, Division of Compensation Analysis 

and Support, Cincinnati, Ohio, March 12, 2015. 

ORAUT 2009. MS Excel workbook, INEL-Actinide Ratios, Revision 0, Oak Ridge Associated 

Universities Team, Oak Ridge Tennessee. December 18, 2009. [SRDB Ref. ID 77440] 

ORAUT-TKBS-0007-5. 2010. Idaho National Laboratory and Argonne National Laboratory – 

West - – Occupational Internal Dose, Revision 03, Oak Ridge Associated Universities Team, 

Cincinnati, Ohio. March 2, 2010. 

ORAUT-OTIB-0054. 2015. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Revision 03, Oak Ridge Associated 

Universities, Cincinnati, Ohio. February 6, 2015. 

SC&A 2015. SC&A’s Evaluation of the NIOSH ER Proposed Use of FAP Bioassay Indicator 

Radionuclides (in Conjunction with OTIB-54 and ORAUT-TKBS-0007-5) for Assessment of FAP 

and Actinide intakes at INL. November 10, 2015. SC&A, Inc., Vienna, Virginia, and Saliant, 

Inc., Jefferson, Maryland. 
Effective Date:

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APPENDIX A: CS-137/SR-90 VALUES FOR MAJOR INL FACILITIES

Figure A-1. CFA Cs-137/Sr-90 

CFA, WMC, D&D, and INL in General

 Waste Documents 1955-1995

0.1

1.0

10.0

100.0

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.15 to <0.5] Cs/Sr [0.5 to 2.0] Cs/Sr [>2.0 to 88]

Figure A-2. ICPP Cs-137/Sr-90 

ICPP 

Waste Documents 1955-1962 & 1975-1995

0.1

1.0

10.0

100.0

1000.0

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.26 to <0.5] Cs/Sr [0.5 to 2.0] Cs/Sr [>2.0 to 150]
Effective Date:

06/24/2016

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0 (Draft)

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Figure A-3. TAN & ANP Cs-137/Sr-90 

TAN & ANP

 Waste Documents 1955-1995

0.01

0.10

1.00

10.00

100.00

1000.00

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.04 to <0.5] Cs/Sr [0.5 to 2.0] Cs/Sr [>2.0 to 225]

Figure A-4. TRA Cs-137/Sr-90 

TRA (MTR, ETR, ATR, PBF, & SPERT)

 Waste Documents 1955-1995

0.1

1.0

10.0

100.0

1,000.0

10,000.0

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.01 to <0.5] Cs/Sr [0.5 to 2.0] Cs/Sr [>2.0 to 2,587]
Effective Date:

06/24/2016

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0 (Draft)

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Figure A-5. INL Cs-137/Sr-90 

All of INL

 Waste Documents 1955-1995

0.01

0.10

1.00

10.00

100.00

1,000.00

10,000.00

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Cs-137/Sr-90

Cs/Sr [0.04 to <0.5] Cs/Sr [Range 0.5 to 2.0] Cs/Sr [>2.0 to 2,587]
Effective Date:

06/24/2016

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0 (Draft)

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APPENDIX B: ACTINIDE/SR-90 VALUES

Figure B-1. INL Am-241/Sr-90 

Figure B-2. INL Pu-238/Sr-90 

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Am-241/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of Am/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of Am/Sr

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1970 1975 1980 1985 1990 1995

Recorded Data Point

Ratio

All of INL (Pu-238/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of Pu238/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of Pu238/Sr
Effective Date:

06/24/2016

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0 (Draft)

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Figure B-3. INL Pu-239/Sr-90 

Figure B-4. INL U-234/Sr-90 

1.E-10

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Pu-239/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of Pu239/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of Pu239/Sr

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (U-234/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of U234/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of U234/Sr
Effective Date:

06/24/2016

Revision No.

0 (Draft)

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Figure B-5. INL U-236/Sr-90 

1.E-12

1.E-11

1.E-10

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (U-236/Sr-90)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-22 of U236/Sr

Ratio [0.5 - 2.0] of Meas to Table 5-22 of U236/Sr
Effective Date:

06/24/2016

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0 (Draft)

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APPENDIX C: ACTINIDE/CS-137 VALUES

Figure C-1. INL Am-241/Cs-137 

Figure C-2. INL Pu-238/Cs-137 

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Am-241/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of Am/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of Am/Cs

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Pu-238/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of Pu238/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of Pu238/Cs
Effective Date:

06/24/2016

Revision No.

0 (Draft)

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Figure C-3. INL Pu-239/Cs-137 

Figure C-4. INL U-234/Cs-137 

1.E-10

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (Pu-239/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of Pu239/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of Pu239/Cs

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (U-234/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of U234/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of U234/Cs
Effective Date:

06/24/2016

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0 (Draft)

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Figure C-5. INL U-236/Cs-137 

1.E-13

1.E-12

1.E-11

1.E-10

1.E-09

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1970 1975 1980 1985 1990 1995

Ratio

Recorded Data Point

All of INL (U-236/Cs-137)

Waste Documents 1970-1995

 Ratio [<0.5 or >2.0] of Meas to Table 5-23 of U236/Cs

Ratio [0.5 - 2.0] of Meas to Table 5-23 of U236/Cs
Effective Date:

06/24/2016

Revision No.

0 (Draft)

Document No./Description:

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ATTACHMENT 1. DOCUMENTS AND DATA USED IN EVALUATION 

OF CS/SR AND ACTINIDES

List of Documents Used from SRBD

Ref ID # Document File Name

85575 085575_Radioactive Waste Reports 1967–1968.pdf

86962 086962_Radioactive Waste Reports 1959.pdf

86970 086970_ICPP Radioactive Waste Reports 1959.pdf

86971 086971_ANP Radioactive Waste Reports 1959.pdf

86973 086973_ETR Radioactive Waste Reports 1959.pdf

86991 086991_SPERT Radioactive Waste Reports 1959.pdf

87007 087007_NRTS Radioactive Waste Reports 1959.pdf

87014 087014_MTR (and ETR Liquids) Radioactive Waste Reports 1960.pdf

87029 087029_ICPP Radioactive Waste Reports 1960.pdf

87191 87191_Radioactive Waste Management for 1985

87203 087203_Radioactive Waste Reports ANP Facility 1960.pdf

87204 087204_Radioactive Waste Reports 1961.pdf

87211 087211_Radioactive Waste Reports ICPP Facility 1961.pdf

87231 087231_Radioactive Waste Reports ICPP Facility 1962.pdf

87258 087258_Radioactive Waste Reports MTR (and ETR Liquids) Facility 1962.pdf

87904 87904_Waste Data for the National Reactor Testing Station Idaho

88069 88069_Radioactive Waste Management Information for 1991 and Record-to-Date

118841 118841_Radioactive Waste Management Information for 1978

136493 136493_Radioactive Waste Management Information for 1993 and Record to Date

138091 138091_ICPP Monthly Radioactive Waste Reports 1959.pdf

138095 138095_ICPP Monthly Radioactive Waste Reports 1960.pdf

138096 138096_ICPP Monthly Radioactive Waste Reports 1961.pdf

138098 138098_ICPP Monthly Radioactive Waste Reports 1962.pdf

138732 138732_SPERT Radioactive Waste Reports January - November 1963.pdf

138736 138736_Solid Radioactive Waste Report MTR and ETR Liquid January - October.pdf

138739 138739_Solid Radioactive Waste Report TAN January - December 1963.pdf

138892 138892_Radioactive Waste Reports, MTR Liquid and Airborne and ETR Liquid.pdf

139139 139139_Radioactive Waste Reports MTR (liquid, airborne, solid) and ETR.pdf

139151 139151_Radioactive Waste Reports TAN-STEP June 1962 - December 1962.pdf

139175 139175_ICPP Monthly Radioactive Waste Reports 1957.pdf

139182 139182_SPERT I Radioactive Waste Reports 1960.pdf

139839 139839_NRTS Radioactive Waste Management Information for 1971

140037 140037_NRTS Radioactive Waste Management Information for 1973

140039 140039_Idaho National Engineering Laboratory Radioactive Waste Management Information for 1974

140040 140040_Idaho National Engineering Laboratory Radioactive Waste Management Information for 1975
Effective Date:

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Summary of Data Used from SRBD Documents

SRDB

Ref #

Pdf

#

Time

period Area

Type of

waste

Meas.

Sr-90

Meas.

Cs-137 Units

Sr90/

Cs-137

Cs-137/

Sr-90

139175 16 1957 ICPP liq 0.01 1.5 % 0.01 150.00

139175 24 1957 ICPP liq 0.04 5 % 0.01 125.00

86962 16 1959 MTR&ETR liq 5.00E-08 1.60E-06 uCi/ml 0.03 32.00

86970 5 1959 ICPP liq 8.50E-09 1.43E-08 uCi/ml 0.59 1.68

86970 7 1959 ICPP liq 2.30E-06 9.10E-07 uCi/ml 2.53 0.40

86970 8 1959 ICPP liq 7.10E-08 4.20E-07 uCi/ml 0.17 5.92

86970 9 1959 ICPP liq 3.90E-07 3.35E-07 uCi/ml 1.16 0.86

86970 11 1959 ICPP liq 1.70E-07 6.00E-06 uCi/ml 0.03 35.29

86970 12 1959 ICPP liq 2.70E-06 7.40E-07 uCi/ml 3.65 0.27

86970 13 1959 ICPP liq 3.80E-06 6.80E-06 uCi/ml 0.56 1.79

86971 2 1959 ANP liq 1.28E-07 6.38E-07 none 0.20 4.98

86971 3 1959 ANP liq 3.09E-07 8.12E-07 none 0.38 2.63

86971 4 1959 ANP liq 3.15E-07 6.70E-07 none 0.47 2.13

86971 5 1959 ANP liq 1.01E-06 2.38E-06 none 0.42 2.36

86973 14 1959 ETR liq 0.27 0.89 mCi 0.30 3.30

86991 5 1959 SPERT liq 2.00E-07 5.60E-06 uCi/ml 0.04 28.00

87007 7 1959 MTR&ETR liq 5.00E-08 1.60E-06 uCi/ml 0.03 32.00

138091 5 1959 ICPP liq 8.50E-09 1.43E-08 uCi/ml 0.59 1.68

138091 7 1959 ICPP liq 2.30E-06 9.10E-07 uCi/ml 2.53 0.40

138091 9 1959 ICPP liq 3.90E-07 3.35E-07 uCi/ml 1.16 0.86

138091 10 1959 ICPP liq 3.90E-07 1.90E-06 uCi/ml 0.21 4.87

138091 11 1959 ICPP liq 1.70E-07 6.00E-06 uCi/ml 0.03 35.29

138091 12 1959 ICPP liq 2.70E-06 7.40E-07 uCi/ml 3.65 0.27

138091 13 1959 ICPP liq 3.80E-06 6.80E-06 uCi/ml 0.56 1.79

139139 13 1959 MTR&ETR liq 5.00E-08 1.60E-06 uCi/ml 0.03 32.00

87014 8 1960 MTR&ETR liq 1.20E-07 4.30E-05 uCi/ml 0.00 358.33

87014 16 1960 MTR&ETR liq 1.50E-06 9.50E-05 uCi/ml 0.02 63.33

87014 18 1960 MTR&ETR liq 1.20E-07 9.20E-06 uCi/ml 0.01 76.67

87029 13 1960 ICPP liq 4.66E-08 9.30E-07 uCi/ml 0.05 19.96

87029 14 1960 ICPP liq 3.92E-07 4.10E-06 uCi/ml 0.10 10.46

87029 15 1960 ICPP liq 4.25E-07 6.90E-07 uCi/ml 0.62 1.62

87203 2 1960 ANP liq 5.25E-07 1.70E-06 none 0.31 3.24

87203 3 1960 ANP liq 1.06E-06 1.18E-06 none 0.90 1.11

87203 4 1960 ANP liq 1.40E-07 3.35E-06 none 0.04 23.93

87203 5 1960 ANP liq 4.46E-08 5.00E-07 none 0.09 11.21

87203 6 1960 ANP liq 6.40E-07 3.50E-06 none 0.18 5.47

87203 8 1960 ANP liq 9.89E-07 6.53E-06 none 0.15 6.60

87203 9 1960 ANP liq 8.24E-07 1.58E-05 none 0.05 19.17

87203 10 1960 ANP liq 1.30E-07 1.25E-06 none 0.10 9.62

87203 11 1960 ANP liq 1.29E-06 1.10E-06 none 1.17 0.85

87203 12 1960 ANP liq 2.93E-07 3.06E-06 none 0.10 10.44

87203 13 1960 ANP liq 3.08E-07 4.16E-06 none 0.07 13.51

138095 11 1960 ICPP liq 4.66E-08 9.30E-07 uCi/ml 0.05 19.96

138095 12 1960 ICPP liq 3.92E-07 4.10E-06 uCi/ml 0.10 10.46

138095 13 1960 ICPP liq 4.25E-07 6.90E-07 uCi/ml 0.62 1.62

139182 2 1960 SPERT liq 2.70E-06 5.90E-06 uCi/ml 0.46 2.19

139182 15 1960 SPERT liq 2.80E-06 9.70E-06 uCi/ml 0.29 3.46

87204 6 1961 MTR&ETR liq 1.98E-06 4.32E-06 uCi/ml 0.46 2.18

87204 12 1961 MTR&ETR liq 8.50E-06 8.90E-06 uCi/ml 0.96 1.05

87204 18 1961 MTR&ETR liq 2.70E-06 3.10E-06 uCi/ml 0.87 1.15

87204 26 1961 MTR&ETR liq 4.50E-07 1.17E-05 uCi/ml 0.04 26.00

87204 30 1961 MTR&ETR liq 2.05E-07 1.40E-05 uCi/ml 0.01 68.29

87204 44 1961 MTR&ETR liq 4.00E-07 1.03E-06 uCi/ml 0.39 2.58

87211 2 1961 ICPP liq 2.04E-07 3.06E-06 uCi/ml 0.07 15.00

87211 4 1961 ICPP liq 9.22E-07 7.43E-06 uCi/ml 0.12 8.06

138096 2 1961 ICPP liq 2.04E-07 3.06E-06 uCi/ml 0.07 15.00

138096 3 1961 ICPP liq 9.22E-07 7.43E-06 uCi/ml 0.12 8.06

87904 14 1961 TRA liq 58.4 5.9 Ci 9.90 0.10

87231 2 1962 ICPP liq 7.80E-08 3.90E-08 none 2.00 0.50

87231 3 1962 ICPP liq 7.95E-04 6.77E-04 uCi/ml 1.17 0.85

87231 6 1962 ICPP liq 9.45E-04 6.14E-04 uCi/ml 1.54 0.65

87231 8 1962 ICPP liq 8.95E-04 8.82E-04 uCi/ml 1.01 0.99
Effective Date:

06/24/2016

Revision No.

0 (Draft)

Document No./Description:

SCA-TR-2016-SEC007

Page No.

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NOTICE: This report has been reviewed to identify and redact any information that is protected by the

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.

SRDB

Ref #

Pdf

#

Time

period Area

Type of

waste

Meas.

Sr-90

Meas.

Cs-137 Units

Sr90/

Cs-137

Cs-137/

Sr-90

87231 9 1962 ICPP liq 1.82E-07 5.09E-06 none 0.04 27.97

87231 10 1962 ICPP liq 1.59E-03 1.54E-03 uCi/ml 1.03 0.97

87231 12 1962 ICPP liq 1.86E-03 1.73E-03 uCi/ml 1.08 0.93

87231 14 1962 ICPP liq 1.60E-03 1.59E-03 uCi/ml 1.01 0.99

87231 16 1962 ICPP liq 2.20E-03 1.41E-03 uCi/ml 1.56 0.64

87231 18 1962 ICPP liq 1.63E-03 1.15E-03 uCi/ml 1.42 0.71

87231 20 1962 ICPP liq 9.34E-04 9.41E-04 uCi/ml 0.99 1.01

87231 22 1962 ICPP liq 6.87E-04 9.00E-04 uCi/ml 0.76 1.31

87231 24 1962 ICPP liq 1.14E-03 8.45E-04 uCi/ml 1.34 0.74

87258 2 1962 MTR&ETR liq 8.90E-07 1.30E-05 uCi/ml 0.07 14.61

87258 5 1962 MTR&ETR liq 6.60E-07 8.20E-06 uCi/ml 0.08 12.42

87258 8 1962 MTR&ETR liq 6.00E-07 6.70E-06 uCi/ml 0.09 11.17

87258 10 1962 MTR&ETR liq 6.00E-07 5.00E-06 uCi/ml 0.12 8.33

87258 12 1962 MTR&ETR liq 5.80E-07 1.10E-06 uCi/ml 0.53 1.90

87258 14 1962 MTR&ETR liq 3.50E-07 4.00E-06 uCi/ml 0.09 11.43

87258 16 1962 MTR&ETR liq 7.00E-07 8.00E-06 uCi/ml 0.09 11.43

87258 18 1962 MTR&ETR liq 5.70E-07 1.50E-05 uCi/ml 0.04 26.32

87258 20 1962 MTR&ETR liq 2.00E-08 1.10E-05 uCi/ml 0.00 550.00

87258 22 1962 MTR&ETR liq 9.00E-07 2.70E-06 uCi/ml 0.33 3.00

87258 24 1962 MTR&ETR liq 2.00E-06 1.30E-05 uCi/ml 0.15 6.50

87258 26 1962 MTR&ETR liq 1.50E-06 3.42E-06 uCi/ml 0.44 2.28

138098 4 1962 ICPP liq 6.87E-04 9.00E-04 uCi/ml 0.76 1.31

138098 6 1962 ICPP liq 9.34E-04 9.41E-04 uCi/ml 0.99 1.01

138098 8 1962 ICPP liq 1.63E-03 1.15E-03 uCi/ml 1.42 0.71

138098 10 1962 ICPP liq 2.20E-03 1.41E-03 uCi/ml 1.56 0.64

138098 12 1962 ICPP liq 1.60E-03 1.59E-03 uCi/ml 1.01 0.99

138098 14 1962 ICPP liq 1.86E-03 1.73E-03 uCi/ml 1.08 0.93

138098 15 1962 ICPP liq 1.59E-03 1.54E-03 uCi/ml 1.03 0.97

138098 16 1962 ICPP liq 1.82E-07 5.09E-06 uCi/ml 0.04 27.97

138098 18 1962 ICPP liq 8.95E-04 8.82E-04 uCi/ml 1.01 0.99

138098 20 1962 ICPP liq 9.45E-04 6.14E-04 uCi/ml 1.54 0.65

138098 22 1962 ICPP liq 5.79E-05 1.88E-03 uCi/ml 0.03 32.47

138098 23 1962 ICPP liq 7.80E-08 3.90E-08 uCi/ml 2.00 0.50

138098 24 1962 ICPP liq 7.95E-04 6.77E-04 uCi/ml 1.17 0.85

139151 2 1962 TAN liq 2.16E-06 1.13E-06 uCi/ml 1.91 0.52

139151 3 1962 TAN liq 5.20E-06 2.30E-06 uCi/ml 2.26 0.44

139151 14 1962 TRA liq 40.9 8.1 Ci 5.05 0.20

138732 3 1963 SPERT liq 2.97E-06 6.04E-06 none 0.49 2.03

138736 5 1963 MTR&ETR liq 8.40E-07 5.90E-06 uCi/ml 0.14 7.02

138736 17 1963 MTR&ETR liq 7.20E-07 3.90E-06 uCi/ml 0.18 5.42

138736 19 1963 MTR&ETR liq 5.00E-06 2.50E-05 uCi/ml 0.20 5.00

138736 21 1963 MTR&ETR liq 5.20E-07 9.60E-06 uCi/ml 0.05 18.46

138736 23 1963 MTR&ETR liq 7.00E-07 9.00E-07 uCi/ml 0.78 1.29

138739 3 1963 TAN liq 1.01E-09 2.27E-07 none 0.00 224.75

138739 7 1963 TAN air 2.86E-11 6.10E-12 none 4.69 0.21

138739 9 1963 TAN air 3.58E-12 1.85E-12 uCi/ml 1.94 0.52

138739 12 1963 TAN air 5.73E-11 8.18E-11 none 0.70 1.43

138739 15 1963 TAN air 8.30E-12 1.41E-11 uCi/ml 0.59 1.70

138739 18 1963 TAN air 3.39E-12 2.65E-12 uCi/ml 1.28 0.78

138739 29 1963 TAN liq 1.44E-06 2.27E-06 uCi/ml 0.63 1.58

138739 32 1963 TAN liq 1.36E-06 1.55E-06 uCi/ml 0.88 1.14

138739 35 1963 TAN liq 2.27E-07 1.70E-06 uCi/ml 0.13 7.49

138892 2 1963 MTR&ETR liq 1.60E-06 1.60E-06 uCi/ml 1.00 1.00

138892 14 1963 TRA liq 47.3 6.7 Ci 7.06 0.14

138892 14 1964 TRA liq 17.3 4.7 Ci 3.68 0.27

138892 14 1965 TRA liq 27.8 6.0 Ci 4.63 0.22

138892 14 1966 TRA liq 29.2 4.0 Ci 7.30 0.14

138892 18 1966 TAN liq 0.01 0.02 Ci 0.50 2.00

85575 10 1967 CFA liq 4.00E-06 6.10E-06 uCi/ml 0.66 1.53

85575 19 1967 TAN air 1.27E-11 4.10E-12 uCi/ml 3.10 0.32

85575 25 1967 CFA liq 1.14E-06 3.10E-06 uCi/ml 0.37 2.72

85575 40 1967 TAN liq 1.60E-07 1.58E-07 uCi/ml 1.01 0.99

85575 54 1967 TAN liq 4.68E-07 1.48E-06 uCi/ml 0.32 3.16

85575 55 1967 TAN air 1.89E-12 6.15E-13 uCi/ml 3.07 0.33
Effective Date:

06/24/2016

Revision No.

0 (Draft)

Document No./Description:

SCA-TR-2016-SEC007

Page No.

29 of 31

NOTICE: This report has been reviewed to identify and redact any information that is protected by the

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.

SRDB

Ref #

Pdf

#

Time

period Area

Type of

waste

Meas.

Sr-90

Meas.

Cs-137 Units

Sr90/

Cs-137

Cs-137/

Sr-90

85575 70 1967 TAN liq 1.05E-06 2.37E-06 uCi/ml 0.44 2.26

85575 79 1967 TAN liq 2.38E-06 3.43E-05 none 0.07 14.41

85575 86 1967 CFA liq 3.40E-08 3.00E-06 uCi/ml 0.01 88.24

85575 14 1967 TRA liq 51.6 5.2 Ci 9.92 0.10

85575 18 1967 TAN liq 0.04 0.36 Ci 0.11 9.00

85575 98 1968 TAN liq 2.81E-07 8.46E-07 uCi/ml 0.33 3.01

85575 102 1968 TRA liq 9.10E-07 9.14E-06 none 0.10 10.04

85575 116 1968 TAN liq 4.20E-07 1.25E-06 uCi/ml 0.34 2.96

85575 130 1968 TAN liq 1.88E-07 2.94E-07 uCi/ml 0.64 1.56

85575 131 1968 TAN air 7.12E-14 4.94E-14 uCi/ml 1.44 0.69

85575 136 1968 TRA liq 9.10E-07 3.28E-06 uCi/ml 0.28 3.60

85575 150 1968 TAN air 4.07E-13 1.02E-13 uCi/ml 3.99 0.25

85575 163 1968 TAN liq 4.52E-07 6.26E-07 uCi/ml 0.72 1.38

85575 165 1968 TAN liq 2.70E-06 4.59E-05 uCi/ml 0.06 17.00

85575 180 1968 TAN air 2.37E-13 1.02E-14 uCi/ml 23.24 0.04

85575 189 1968 TAN liq 3.29E-06 6.13E-06 uCi/ml 0.54 1.86

85575 214 1968 TAN air 6.16E-13 3.08E-13 uCi/ml 2.00 0.50

85575 217 1968 TAN liq 8.10E-08 5.64E-07 uCi/ml 0.14 6.96

85575 218 1968 TAN air 4.53E-12 7.55E-12 uCi/ml 0.60 1.67

85575 230 1968 TAN air 1.52E-13 1.22E-13 uCi/ml 1.25 0.80

85575 231 1968 TAN liq 2.70E-08 3.42E-07 uCi/ml 0.08 12.67

85575 243 1968 TAN liq 1.77E-08 1.55E-07 uCi/ml 0.11 8.76

85575 244 1968 TAN air 2.10E-13 5.10E-14 uCi/ml 4.12 0.24

85575 256 1968 TRA liq 1.32E-07 7.17E-07 uCi/ml 0.18 5.43

85575 257 1968 TAN air 5.54E-14 1.54E-13 uCi/ml 0.36 2.77

85575 262 1968 TAN liq 2.17E-07 6.90E-07 uCi/ml 0.31 3.18

85575 269 1968 TRA liq 2.34E-05 3.97E-05 uCi/ml 0.59 1.70

85575 14 1968 TRA liq 22.0 4.2 Ci 5.24 0.19

85575 18 1968 TAN liq 0.02 0.046 Ci 0.43 2.30

85575 14 1969 TRA liq 32.8 11.4 Ci 2.88 0.35

85575 18 1969 TAN liq 0.03 0.06 Ci 0.50 2.00

139839 10 1971 INEL air 1.44E+01 1.52E+01 Ci 0.95 1.05

139839 10 1971 INEL liq 1.47E+01 1.06E+01 Ci 1.38 0.72

139839 10 1971 INEL solid 1.68E+01 4.01E+02 Ci 0.04 23.87

139839 43 1971 TRA liq 2.01E-05 1.40E-05 uCi/ml 1.44 0.69

139839 46 1971 TRA solid - 4.298 Ci 0.23 -

139839 55 1971 TRA air 5.97E-04 3.54E-03 Ci 0.17 5.93

139839 57 1971 TAN liq 7.50E-08 1.97E-07 uCi/ml 0.38 2.62

139839 58 1971 TAN solid 6.20E-01 5.34E+01 Ci 0.01 86.19

140037 9 1973 INEL air 1.848 5.357 Ci 0.34 2.90

140037 9 1973 INEL liq 4.475 3.931 Ci 1.14 0.88

140037 9 1973 INEL solid 1.87E+02 8.95E+02 Ci 0.21 4.78

140037 45 1973 TRA liq 4.16E-06 3.86E-06 uCi/ml 1.08 0.93

140037 57 1973 TAN air 2.11E-13 5.63E-14 uCi/ml 3.75 0.27

140037 59 1973 TAN solid 1.302 2.84E-01 Ci 4.58 0.22

140039 11 1974 INEL air 3.195 6.731 Ci 0.47 2.11

140039 11 1974 INEL liq 5.242 4.117 Ci 1.27 0.79

140039 11 1974 INEL solid 1.58E+03 1.42E+03 Ci 1.11 0.90

140039 65 1974 TRA liq 3.19E-07 3.70E-06 uCi/ml 0.09 11.58

140039 83 1974 TAN air 1.78E-13 1.36E-13 uCi/ml 1.30 0.77

140039 84 1974 TAN liq 7.06E-08 1.14E-08 uCi/ml 6.22 0.16

140039 85 1974 TAN solid 1.54E+01 2.24E+02 Ci 0.07 14.58

140039 87 1974 CFA liq 2.09E-07 2.00E-07 uCi/ml 1.05 0.96

140039 146 1974 TRA liq 6.16E-07 5.08E-06 uCi/ml 0.12 8.25

140039 163 1974 TAN liq 9.64E-08 1.68E-08 uCi/ml 5.75 0.17

140039 164 1974 TAN solid 1.03E+01 1.44E+02 Ci 0.07 13.99

140039 166 1974 CFA liq 3.18E-07 2.03E-07 uCi/ml 1.57 0.64

140040 9 1975 INEL air 2.43E-01 5.97E-01 Ci 0.41 2.46

140040 9 1975 INEL liq 4.74E-01 3.16 Ci 0.15 6.67

140040 9 1975 INEL solid 2.16E+02 5.70E+02 Ci 0.38 2.64

140040 90 1975 TRA liq 3.8 2.649 Ci 1.43 0.70

140040 95 1975 TRA solid - 6.16E-01 Ci - -

140040 109 1975 PBF liq 4.82E-09 1.53E-07 uCi/ml 0.03 31.76

140040 114 1975 TAN air 4.00E-14 2.24E-14 uCi/ml 1.79 0.56
Effective Date:

06/24/2016

Revision No.

0 (Draft)

Document No./Description:

SCA-TR-2016-SEC007

Page No.

30 of 31

NOTICE: This report has been reviewed to identify and redact any information that is protected by the

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.

SRDB

Ref #

Pdf

#

Time

period Area

Type of

waste

Meas.

Sr-90

Meas.

Cs-137 Units

Sr90/

Cs-137

Cs-137/

Sr-90

140040 116 1975 TAN liq 2.11E-08 9.55E-09 uCi/ml 2.21 0.45

140040 117 1975 TAN solid 4.371 9.763 Ci 0.45 2.23

140040 119 1975 CFA liq 7.31E-08 1.80E-07 uCi/ml 0.41 2.47

140040 122 1975 CPP air 1.75E-10 4.30E-10 uCi/ml 0.41 2.46

140040 125 1975 CPP liq 4.42E-07 4.59E-07 uCi/ml 0.96 1.04

140040 128 1975 CPP solid 1.71E+02 5.03E+02 Ci 0.34 2.93

118841 11 to 14 1978 INEL air 2.39E-02 8.58E-02 Ci 0.28 3.59

118841 11 to 14 1978 INEL liq 3.972 8.966 Ci 0.44 2.26

118841 11 to 14 1978 INEL solid 1.13E+03 2.96E+03 Ci 0.38 2.61

118841 80-81 1978 TRA air 2.97E-05 1.01E-05 Ci 2.95 0.34

118841 82-83 1978 TRA liq 7.15E-06 1.47E-05 uCi/ml 0.49 2.06

118841 97-98 1978 PBF air 1.81E-14 1.16E-12 uCi/ml 0.02 63.94

118841 100-103 1978 PBF liq 2.65E-07 2.22E-05 uCi/ml 0.01 83.89

118841 106 1978 TAN air 2.46E-05 4.80E-05 Ci 0.51 1.95

118841 108 1978 TAN liq 6.28E-08 1.80E-08 uCi/ml 3.48 0.29

118841 110 1978 TAN air 3.36E-14 7.67E-14 uCi/ml 0.44 2.28

118841 112 1978 Decon air 6.78E-15 6.26E-15 uCi/ml 1.08 0.92

118841 117 1978 TRA air 3.43E-13 1.23E-13 uCi/ml 2.80 0.36

118841 121 1978 ICPP air 1.56E-11 5.62E-11 uCi/ml 0.28 3.59

118841 125 1978 ICPP liq 3.64E-07 1.24E-06 uCi/ml 0.29 3.42

118841 127 1978 ICPP solid 1.04E+03 2.56E+03 Ci 0.41 2.46

118841 189 1978 WMC solid 4.80E+00 1.20E+00 Ci 4.00 0.25

87191 22 1985 INEL air 1.90E-03 6.22E-03 Ci 0.31 3.27

87191 22 1985 INEL liq 5.08E-02 2.29E-01 Ci 0.22 4.50

87191 22 1985 INEL solid 2.81E+01 4.68E+02 Ci 0.06 16.63

87191 93 1985 TRA air 6.46E-16 1.67E-12 uCi/ml 0.00 2587.49

87191 97 1985 TRA liq 3.70E-07 2.44E-06 uCi/ml 0.15 6.60

87191 109 1985 MTR air 1.72E-15 3.41E-14 uCi/ml 0.05 19.85

87191 118 1985 TRA air 1.77E-13 3.92E-12 uCi/ml 0.05 22.09

87191 120 1985 PBF air 9.82E-14 1.26E-12 uCi/ml 0.08 12.87

87191 127 1985 TAN air 1.63E-14 1.28E-15 uCi/ml 12.76 0.08

87191 130 1985 TAN air 1.96E-13 1.44E-14 uCi/ml 13.58 0.07

87191 133 1985 CFA air 5.76E-14 5.17E-14 uCi/ml 1.11 0.90

87191 154 1985 CPP air 5.68E-13 1.32E-12 uCi/ml 0.43 2.33

87191 157 1985 CPP liq 1.07E-08 1.40E-08 uCi/ml 0.77 1.31

87191 160 1985 CPP solid 9.713 9.713 Ci 1.00 1.00

87191 162 1985 CPP liq 4.56E-10 1.59E-09 uCi/ml 0.29 3.49

87191 164 1985 CPP liq 1.07E-08 1.40E-08 uCi/ml 0.77 1.31

87191 167 1985 CPP air 1.32E-11 3.13E-11 uCi/ml 0.42 2.37

88069 185 1991 CFA air 4.55E-15 6.99E-16 uCi/ml 6.51 0.15

88069 192 1991 CFA air 4.55E-15 7.55E-16 uCi/ml 6.03 0.17

88069 206 1991 CPP air 8.44E-13 7.16E-12 uCi/ml 0.12 8.48

88069 209 1991 CPP liq 4.08E-09 1.06E-09 uCi/ml 3.86 0.26

88069 211 1991 CPP solid 2.36E+00 2.36E+00 Ci 1.00 1.00

88069 236 1991 CPP liq 4.08E-09 1.06E-09 uCi/ml 3.86 0.26

88069 305 1991 PBF air 1.16E-15 9.51E-15 uCi/ml 0.12 8.18

88069 383 1991 TRA air 5.07E-15 1.20E-14 uCi/ml 0.42 2.37

88069 388 1991 TRA liq 1.09E-08 2.19E-08 uCi/ml 0.50 2.01

88069 391 1991 TRA solid 3.58E-01 5.19E+01 Ci 0.01 144.81

88069 454 1991 WER air 9.29E-15 1.42E-14 uCi/ml 0.65 1.53

136493 214 1993 CFA solid 8.55E-05 7.40E-03 Ci 0.01 86.50

136493 245 1993 CPP air 2.49E-13 1.77E-12 uCi/ml 0.14 7.09

136493 247 1993 CPP liq 1.09E-09 8.66E-10 uCi/ml 1.26 0.79

136493 248 1993 CPP solid 7.20E-03 7.20E-03 Ci 1.00 1.00

136493 288 1993 D&D solid 8.27E-01 4.78E-01 Ci 1.73 0.58

136493 451 1993 TAN air 1.55E-15 7.08E-15 uCi/ml 0.22 4.58

136493 453 1993 TAN solid 5.41E-02 2.633 Ci 0.02 48.68

136493 480 1993 TRA air 9.81E-16 5.29E-15 uCi/ml 0.19 5.39

136493 484 1993 TRA liq 1.58E-06 1.11E-06 uCi/ml 1.42 0.71

136493 487 1993 TRA solid 8.526 1.475 Ci 5.78 0.17

136493 512 1993 ATR solid 8.526 1.475 Ci 5.78 0.17

136493 519 1993 MTR air 7.78E-16 4.73E-16 uCi/ml 1.65 0.61

136493 522 1993 TRA solid - 6.30E-05 Ci 15873.02 -

136493 524 1993 TRA liq 1.58E-06 1.11E-06 uCi/ml 1.42 0.71
Effective Date:

06/24/2016

Revision No.

0 (Draft)

Document No./Description:

SCA-TR-2016-SEC007

Page No.

31 of 31

NOTICE: This report has been reviewed to identify and redact any information that is protected by the

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.

SRDB

Ref #

Pdf

#

Time

period Area

Type of

waste

Meas.

Sr-90

Meas.

Cs-137 Units

Sr90/

Cs-137

Cs-137/

Sr-90

136493 557 1993 WER solid - 3.40E-03 Ci 294.55 -

136493 578 1993 WER solid - 3.40E-03 Ci 294.55 -

Note: Entries with hyphens represents data points w/o Sr-90 values but contained Cs-137 & actinide values that were used in this 

report.